Abstract
This study evaluated experimentally the influence of the swirling inflow condition upon the flow field in the cold leg piping, which comprises three 90 ° elbows, of the primary cooling system of Japan sodium-cooled fast reactor. Flow visualization experiment was conducted to reveal the velocity fields of the flow in the piping with swirling flow generator. When comparing to the developed turbulent inflow case, the flow separations in the intrados of the 1st elbow became smaller and the swirling flow downstream of the 2nd elbow became stronger, and there appeared separated regions downstream of the 2nd elbow which was not observed in developed turbulent inflow case. Since the flow separation can be considered as the source of the separated vortices which induce pressure fluctuations, these results imply the possibility that pressure fluctuations downstream of the 1st elbow are reduced and those of the 2nd elbow are enhanced by swirling flows as the inlet condition. The separated region is strongly reduced when a suitable swirling inflow enters the 3rd elbow.
Original language | English |
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Pages (from-to) | 7233-7238 |
Number of pages | 6 |
Journal | International Journal of Hydrogen Energy |
Volume | 41 |
Issue number | 17 |
DOIs | |
Publication status | Published - 2016 May 11 |
Keywords
- Fast reactor
- Flow separation
- Flow-induced vibration
- Swirling flow
ASJC Scopus subject areas
- Renewable Energy, Sustainability and the Environment
- Fuel Technology
- Condensed Matter Physics
- Energy Engineering and Power Technology